ML20079Q313
| ML20079Q313 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/05/1983 |
| From: | Lin D COMMONWEALTH EDISON CO. |
| To: | |
| Shared Package | |
| ML20079Q299 | List: |
| References | |
| NUDOCS 8305110452 | |
| Download: ML20079Q313 (13) | |
Text
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LASALLE NUCLEAR POWER STATION UNIT 1 MONTHLY PERFORB1ANCE REPORT APRIL 1983 COFDIONWEALTH EDISON COMPANY NRC DOCKET NO. 050-373 LICENSE NO. NPF-ll l
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8305110452 830505 PDR ADOCK 05000373 R
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TABLE OF CONTENTS 1.
INTRODUCTION II.
SUMMARY
OF OPERATING EXPERIENCE FOR UNIT ONE III. PLANT OR PROCEDURE C11ANGES, TESTS, EXPERIMENTS, AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications B.
Facility or Procedure Changes Requiring NRC Approval C.
Tests and Experiments Requiring NRC Approval D.
Corrective Maintenance of Safety Related Equipment IV.
LICENSEE EVENT REPORTS V.
DATA TABULATIONS A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions VI.
UNIQUE REPORTING REQUIREMENTS A.
bbin Steam Relief Valve Operations B.
ECCS System Outages C.
Off-Site Dose Calculation Manual Changes D.
Major Changes to Radioactive Waste Treatment System E.
Changes to the Process Control Program
I.
INTRODUCTION The LaSalle Nuclear Power Station Unit One is a Boiling Water Reactor with a designed electrical output of 1078 MWe net, located in Marseilles, Illinois. The Station is owned by Commonwealth Edison Company. The Architect / Engineer was Sargent & Lundy, and the primary construction contractor was Commonwealth Edison Company.
The condenser cooling method is a closed cycle cooling pond.
The plant is subject to License Number NPF-11, issued on April 17, 1982. The date of initial criticality was June 21, 1982.
The unit has not commenced commercial generation of power.
This report was complied by Diane L. Lin, telephone number (815)357-6761, extension 499.
II.
SUMMARY
OF UNIT OPERATING EXPERIENCE FOR UNIT ONE April 1-5 The unit was shutdown due to receiving the IRM B Hi alarm and Scram on March 30, 1983 April 5-9 The reactor went critical at 0225 hours0.0026 days <br />0.0625 hours <br />3.720238e-4 weeks <br />8.56125e-5 months <br /> on Aprii 5, 1983. At 1417 hours0.0164 days <br />0.394 hours <br />0.00234 weeks <br />5.391685e-4 months <br /> the main generator was synchronized to the grid and loaded.
On April 8,1983 reactor power was 30%. At 0430 on April 9, 1983 the reactor scrammed due to a turbine trip induced by a spurious hydraulic transient in an instrument line during performance of an instrument surveillance.
The reactor was critical for 74 hours8.564815e-4 days <br />0.0206 hours <br />1.223545e-4 weeks <br />2.8157e-5 months <br /> and 5 minutes.
April 10-30 The reactor went critical at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on April 10, 1983. At 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br /> the main generator was synchronized to the grid and loaded to 42% power.
On April 12, 1983 at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br /> power was reduced to 13% to isolate half of the main condenser.
On April 14 at 0100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />, power was increased to 70%. At 1637 hours0.0189 days <br />0.455 hours <br />0.00271 weeks <br />6.228785e-4 months <br /> on April 14, 1983 the reactor auto scrammed on low level.
This outage was extended due to condenser repairs and the recirculation seals being replaced. The reactor was critical for 97 hours0.00112 days <br />0.0269 hours <br />1.603836e-4 weeks <br />3.69085e-5 months <br /> and 7 minutes.
i III. PLANT OR PROCEDURE CHANGES, TESTS, EXPERIMENTS AND SAFETY RELATED MAINTENANCE A.
Amendments to Facility License or Technical Specifications.
Amendment 13 - This amendment grants a change to the Technical Specifications which allows a reduction of level requirements for the carbon dioxide storage tanks.
B.
Facility or Procedure Changes Requiring NRC Approval.
There were no facility or procedure changes requiring NRC approval during the reporting period.
C.
Tests and Experiments Requiring NRC Approval.
There were no tests or experiments requiring NRC approval during the reporting period.
D.
Corrective Maintenance of Safety Related Equipment.
The following tables present a summary of safety-related maintenance completed on Unit One during the reported period.
The headings indicated in this summary include: Work Request Numbers, LER Numbers, Component Name, Cause of Malfunctions, Results and Effects on Safe Operation, and Corrective Action.
VORK REQUEST LER C0llP0llEllT CAUSE OF HALFUllCTIO!I RESULTS All0 EFFECTS CORRCCilVI. ACIl0ll Oil SAFE OPERATl0ll L18346 RIIR Suction Valve Bad overload relay Valve trips Replaced overload relay L21332 "A" Ril Injection Bad packing Valve leaks Replaced valve Valve L22300 RCIC Vacuum Breaker Bad.annon'diator input card Valve not full open alarm Replaced annunciator Outboard Isolation did not come up when valve input card Valve cycled closed L23285'
,'1 83-029/03L-0 MSIV Low Pressure Switch calibrated to wrong No effect Performed switch Isolation value contact response time test J
L23292 f
Drywell Air and Slip ring loose Cha r.t drive did not work Tightened slip ring Suppression Pool properly Temperature Recorder L23462 83-021/OlT-0 Hydrogen Recombiners Cause unknown.,
Circuit breakers have over-Removed circuit L23463 for Units 1 and 2 load trip and reset breaker #13 problem L23644 Drywell Equipment Actuator arm out-of-posi-Wrong valve indication Realigned arm and Drain Sump Isolation tion and loose
/
tightened Valve L23708 83-032/03L-0 Turbine Stop Valve Limit switch needed to be Want switch to actuate when Rotated limit Limit Switch rotated valve is 95% open or switch 10 greater L23822 1RE026 Limit switch actuator Limit switch for closed Tightened limit Joose indication sticking when switch valve is closed o
I L23846 Reactor Level Indi-Bad valve Valve will not seat Replace valve cation Valve L23945 Drywell Air and Bad pinion gear Reacorder does not drive Replaced pinion Suppression Pool properly gear Temperature Recorder
VORF REQUEST LER CollP0llEllT CAUSE Cf flAl.fullCT10ll RESULTS AllD EFFECTS CORRLCIIV. ACl~10ll O!! SAFE OPERATI0li L24030 Startrec lsolators Out-of-calibration No'effect Recalibrated L24078 Diesel Generator Bad connectors No effect Fixed connectors Room Vent System "VD" Local Control
~~
Panel L24124 IB Diesel Generator Several l_alts loose Exhaust leak Retorqued bolt Exhaust l
L2415$ d RilR IIeat Exchanger B Out-of-calibration No effect Recalibrated loop l
4 Level Transmitter I
f Dampers OVE08YA Upper seal leaking on Dampers remained closed and Replaced seal L24311 and OVE07YA shaft oped respectively L24312 4
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IV.
LICENSEE EVENT REPORTS The following is a tabular summary of all licensee event reports for LaSalle Nuclear Power Station, Unit One, occurring during the reporting period, April 1 to April 30, 1983. This information is provided pursuant to the reportable occurrence reporting require-ments as set forth in section 6.6.B.1 and 6.6.B.2 of the Technical Specifications.
Licensee Event Report Number Date Title of Occurrence 83-021/01T-0 3-23-83 Unit 1 and 2 Hydrogen Recombiners 83-022/03L-0 3/17/83 Vessel Cooldown in Excess of 100 /hr 83-023/03L-0 3/10/83 Rx Vessel Water Level High HPCS Injection Valve Closure 83-024/03L-0 3/12/83 Rod 18-15 Overtravel 83-025/03L-0 3/15/83 Loss of 1B Off Gas H Analyzer 2
83-026/03L-0 3/21/83 Radwaste Discharge PRM Inop 83-027/03L-0 3/20/83 control Valve #1 Steam Feed Leak Off Line Weld Leak 83-028/03L-0 3/20/83 "1A" OG SJAE Drain Line Weld Leak 83-029/03L-0 3/17/83 Response Time for MSlV Isolation on Low Pressure 83-030/03L-0 3/24/83 CRD Removal Eatch LLR Surveillance 1
83-031/03L-0 3/24/83 SBGT Flow Transmitter Potential Rod Failure 83-032/03L-0 3/31/83 T.S.V.-R.P.S. Limits Out of Spec 83-033/03L-0 4/2/83 Radwaste Discharge Process Radiation Monitor Inop
I V.
DATA TABULATIONS The following data tabulations are presented in this report:
A.
Operating Data Report B.
Average Daily Unit Power Level C.
Unit Shutdowns and Power Reductions 1
i i
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LTP-300-7 ACACIDfEC D Revision 2 Novedber 13,.1979 9
OPERATING DATA REPORT DCCKET NO.
- 3 U' NIT LaSalle One May 5, 1983 DATE Diane L. Lin COMPLETED BY
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815-357-6761 X499 TELEPHONE OPER ATING STATUS 720
- 1. REPORTING PERIOD:
GROSS. HOURS IN REPORTING PERICO:
100%
M AX. D EPEND. CAPACITY (MWe-Ned:
0
- 2. CURRENTLY AUTHORIZED POWER LEVEL (MWt):
DESIGN ELECTRICAL RATING (MWe Not):
1078 li
- 3. POWER LEVEL TO WHICH R ESTRICTED (IF ANY) (MWe Net):
A REASONS FOR RESTRICTION (lF ANY1:
THIS MONTH YR TO DATE ; CUMULATIVE I71.2 1061.2 4698.6 S. NUM8ER OF HOURS REACTOR WAS CRITICAL..............
i 0
0 0
S. REACTOR RESERVE SHUTDCWN HOURS...
152.9 955.58 2813.28
- 7. HOUR $ G EN E R ATOR O N LI N E..........................
0 0
0
- 6. UNIT RESERVE SHUTOOWN HOURS.....................
183442 1202283 3342862 S. GROSS THERMAL ENERGY GENER ATED (MWM) 52396 337448 857847 l
- 10. GROSS ELECTRICAL ENERGY GENERATED (MWHI....
39699 294666 755441
- 11. NET ELECTRICAL ENERGY GENhaATED (MWM) i N/A N/A N/A
- 12. R EACTO R SE RVICE F ACTO R...........................
N/A N/A N/A
- 13. REACTOR AVAILASILITY F ACTOR.......................
N/A N/A N/A
- 14. UNIT SERVICE F ACTOR..............................
N/A N/A N/A
- 16. UNIT CAPACITY FACTOR (Using MDC).....................
N/A N/A N/A
- 17. UNIT CAPACITY FACTOR (Us.es Owgn MWe)
N/A N/A N/A i
- 18. UNIT FORCED CUTAGE R ATE.........................
9
- 19., SHUTDOWNS SCHEDULED OV ER NEXT 6 MONTHS (TYPE. DATE. AND DURATION OF EACH):
5/16/83
- 20. IF SHUT OOWN AT ENO OF REPCRT PERICO, ESTIMATED DATE OF STARTUP:
- 21. UNITS IN TEST STATUS (PRIOR TO COMMERCIAL CPER ATICN!:
FCRECAST ACHIEVED 6/2l/82 INITI AL CRITICALITY 9/4/82 i
i INITIAL ELECTRICITY 6/1/83 COMMERCI AL OPE R ATION 1
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Revision 2-
, November 13, 1979 5
ATTACHMENT A AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.
050-373 tjNIT LaSalle one
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DATE May 5,'1983 COMPLETED BY Diane L. Lin TELEPHONE 815-357-6761 x499 MONTH April 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (HWe-Ne t)
(MWe-Net) 1.
0 17 o
2.
0 18.
o 3
0 19 o*
4.
0 20.
'o 5
0 21.
o 6.
43 22.
o 7
106 23 o
8.
197 24.
0 9
4s 25 o
10.
o 26.
o 11.
400 27 0
12.
264 28.
n
- 13 421
'29 0
' 14..
~ 496 30.
0 15 0
31.
16.
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E WB 35mlE Liit3 Luz agdes niasm amam LTP-300-7 Revision 2 Novembcr 13, 1979 6
ATTACilHFJIT B UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET HO. 050-373 LaSalle One UNIT NAME DATE ytay 5,1983 l
REPORT HONTH April 1983 Diane L. Lin l
COMPLETED BY 815-357-6761 X499 TELEPl10NE HETHOD OF SilUTTING DOWN TYPE THE REACTOR OR NO.
DATE S: SCllEDULED (IIOURS)
REASON (1)
REDUCING POWER (2)
CORRECTIVE ACTIONS / COMMENTS l
F: FORCED DURATION t
}
4 Rx scram due to IR>l B 111 12 3/30/83 F
134.3 A
Alarm l
3 Rx scram on level. Auto i
l 13 4/9/83 F
41.4 A
l trip of feed water pumps.
1 5
To isolate 1/2 of main O'
A 6
14 4/12/83 F
condenser 3
Rx scram on low level.
15 4/14/83 F
391.3 A
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.. _ _. _. _ _ _ _.. _ _ _ _ _ _ _ _ _ _. _ _ _ _ = _ _ _ = _. - _ _
_ ~ _ _.. _
i V1.
UNIQUE REPORTING REQUIREMENTS l
i A.
Main Steam Relief Valve Operations for Unit 1 1
There were no main steam relief valve operations for the L
l reporting period.
i i
B.
ECCS Systems Outages i
OUTAGE NO.
EQUIPMENT PURPOSE OF OUTAGE 1-375-83 "A" RHR Service Water To lubricate the Water Pump coupling 1-376-83 "B" RHR Service To lubricate the Water Pump coupling i
i 1-384-83 "C" RHR Service To lubricate the Water Pump coupling 1-385-83 "D" RHR Service To lubricate the Water Pump coupling l-400-83 LPCS/RHR "A" Water To lubricate the Leg Pump coupling C.
Off-Site Dose Calculation Manual l
There were no changes to the Off-Site Dose Calculations Manual during this reporting period.
D.
Radioactive Waste Treatment System l
l There were no changes to the Radioactive Waste Treatment System during this reporting period.
I t
E.
There were no changes to the Process Control Program during this reporting period.
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